LA-13638, "A Review of Criticality Accidents"
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KINETIC ANALYSIS of SUB-PROMPT-CRITICAL REACTOR ASSEMBLIES Hy S Das Theoretical Physics Division
BARC/1992/E/011 O 1 "o KINETIC ANALYSIS OF SUB-PROMPT-CRITICAL REACTOR ASSEMBLIES hy S Das Theoretical Physics Division 1992 BARC/1992/E/011 o UJ GOVERNMENT OF INDIA - AATOMIT C ENERGY COMMISSION U KINETIC ANALYSIS OF SUB-PROMPT-CRITICAL REACTOR ASSEMBLIES by S. Das Theoretical Physics Division BHABHA ATOMIC RESEARCH CENTRE BOMBAY, INDIA 1992 BARC/1992/E/011 BIBLIOBRAPHIC DESCRIPTION SHEET FOR TECHNICAL REPORT (as par IS i 94BNB - 1980) 01 Security classification i Unclassified 02 Distribution t External 03 Report status i New 04 Series i BARC External 05 Report type i Technical Report 06 Report No. i BARC/1992/E/011 07 Part No. or Volume No. i 08 Contract No. i 10 Title and subtitle i Kinetic analysis of sub-prompt- critical reactor assemblies 11 Collation i 14 p.f 4 figs., 1 tab. IS Project No. i 20 Personal author<s> i S. Das 21 Affiliation of author(s) i Theoretical Physics Division, Bhabha Atomic Research Centre, Bombay 22 Corporate author(s) i Bhabha Atomic Research Centre, Bombay - 400 085 23 Originating unit i Theoretical Physics Division, BARC, Bombay 24 Sponsor(s) Name i Department of Atomic Energy Type i Government 30 Date of submission i May 1992 31 Publication/Issue date i June 1992 Contd... (ii) 1 40 Publ i»h»r/Distributor t Head, Library and Information Division, Bhabha Atomic Rasaarch Contra, Bombay 42 Form of distribution t Hard Copy 50 Languaga of taxt i English 51 Languaga o-f summary i English 92 No. of references i % rafs. 53 Givas data on i 60 Abstract x Nautronic analysis of safaty-ralatad kinetics problams in experimental neutron multiplying assemblies has bean carried out using a sub-prompt-critical reactor model. -
Security Operational Skills 2 (Tracing).P65
Unit - 4 K Operating Skill for handling Natural Disasters Structure 4.1 Objectives 4.2 Introduction 4.3 Operating Skill for natural and nuclear disasters 4.4 Accident Categories 4.5 Nuclear and radiation accidents and incidents 4.6 Geological disasters 4.7 Operating Skills for handling Mines and other Explosive Devices 4.8 Operating Skills for handing hijacking situation (other than an airline hijacking 4.9 Operating skills for antivehicle theft operations 4.10 Operating skills for facing a kidnapping or hostage situation 4.11 Operating Skill for handling coal mines and other explosive devices 4.12 Hostage Rights : Law and Practice in Throes of Evolution 4.12.1 Terminology 4.13 Relative Value of Rights 4.14 Conflict of Rights and Obligations 4.15 Hong Kong mourns victims of bus hijacking in the Philoppines 4.16 Rules for Successful Threat Intelligence Teams 4.16.1 Tailor Your Talent 4.16.2 Architect Your Infrastructure 4.16.3 Enable Business Profitability 4.16.4 Communicate Continuously 4.17 Construction Safety Practices 4.17.1 Excavation 4.17.2 Drilling and Blasting 4.17.3 Piling and deep foundations 234 4.18 Planning 4.18.1 Steps in Planning Function 4.18.2 Characteristics of planning 4.18.3 Advantages of planning 4.18.4 Disadvantages of planning 4.1 Objectives The following is a list of general objectives departments should consider when creating an Information Disaster Prevention and Recovery Plan: O Ensure the safety of all employees and visitors at the site/facility O Protect vital information and records O Secure business sites -
Multi-Organ Involvement and Failure in Selected Accident Cases with Acute Radiation Syndrome Observed at the Mayak Nuclear Facility
DOI: 10.1259/bjr/84574102 Multi-organ involvement and failure in selected accident cases with acute radiation syndrome observed at the Mayak Nuclear Facility T V AZIZOVA, MD, PhD, N G SEMENIKHINA, MD and M B DRUZHININA Southern Ural Biophysics Institute, Ozyorsk, Russia Abstract. Mayak Production Association (Mayak PA) in the Southern Ural is the first Russian nuclear facility of plutonium production for weapons. Due to the lack of knowledge and experience in operating nuclear facilities, 19 radiation accidents including criticality accidents occurred and 59 individuals developed acute radiation syndrome (ARS) during commissioning and development of Mayak PA (1948–1958). Severe accidents that occurred at this facility are reviewed, and the initial symptoms and clinical courses of ARS in victims are discussed from the perspective of multi-organ involvement and failure. Introduction reactors with fuel rod manipulations. 3 of 19 accidents (16%) were accompanied by a spontaneous chain reaction. Whole body exposure to high doses of radiation causes In 19 accidents, 49 men and 10 women developed ARS, acute radiation syndrome (ARS) involving multiple organs and 6 men and 1 woman died of ARS. and tissues. Development of modern medicine, including intensive care, allows patients highly exposed to radiation to survive longer than before. However, the experience of Criticality accidents at Mayak PA during 1948–1958 the Tokai-mura criticality accident that occurred in Japan in 1999 raised problems in the treatment of heavily A criticality accident involving plutonium nitrate exposed victims. Treatment of the victims in this accident solution in an interim storage vessel has demonstrated that bone marrow failure is not neces- On 15 March 1953 an accident occurred in a building sarily a restricting factor for recovery, but that multi-organ where processing was being carried out to recover involvement and failure is likely to be such a factor. -
Benefit-Function of Two- Identical Cold Standby Nuclear Reactors System Subject to Failure Due to Radioactivity Or Overheating, Steam Explosion, Fire, and Meltdown
International Journal on Mechanical Engineering and Robotics (IJMER) ________________________________________________________________________________________________ Benefit-Function of Two- Identical Cold Standby Nuclear Reactors System subject to failure due to radioactivity or Overheating, steam explosion, fire, and meltdown Ashok Kumar Saini BLJS COLLEGE, TOSHAM (BHIWANI) HARYANA INDIA Email ID [email protected] The accident killed 30 people directly and damaged Abstract- A nuclear and radiation accident is defined by approximately $7 billion of property. A study published in the International Atomic Energy Agency as "an event that 2005 estimates that there will eventually be up to 4,000 has led to significant consequences to people, the additional cancer deaths related to the accident among environment or the facility." Examples include lethal those exposed to significant radiation levels. Radioactive effects to individuals, large radioactivity release to fallout from the accident was concentrated in areas of the environment, or reactor core melt." The prime Belarus, Ukraine and Russia. Approximately 350,000 example of a "major nuclear accident" is one in which people were forcibly resettled away from these areas soon a reactor core is damaged and significant amounts after the accident. of radioactivity are released, such as in the Chernobyl disaster in 1986. Benjamin K. Sovacool has reported that worldwide there have been 99 accidents at nuclear power plants from 1952 The impact of nuclear accidents has been a topic of debate to 2009 (defined as incidents that either resulted in the loss practically since the first nuclear reactors were constructed of human life or more than US$50,000 of property damage, in 1954. It has also been a key factor in public concern the amount the US federal government uses to define about nuclear facilities. -
Total Prompt Energy Release in the Neutron-Induced Fission Of
Nuclear Physics A 772 (2006) 113–137 Total prompt energy release in the neutron-induced fission of 235U, 238U, and 239Pu D.G. Madland Theoretical Division, Los Alamos National Laboratory, Los Alamos, NM 87545, USA Received 12 January 2006; received in revised form 28 March 2006; accepted 29 March 2006 Available online 2 May 2006 Abstract This study addresses, for the first time, the total prompt energy release and its components for the fission of 235U, 238U, and 239Pu as a function of the kinetic energy of the neutron inducing the fission. The com- ponents are extracted from experimental measurements, where they exist, together with model-dependent calculation, interpolation, and extrapolation. While the components display clear dependencies upon the incident neutron energy, their sums display only weak, yet definite, energy dependencies. Also addressed is the total prompt energy deposition in fission for the same three systems. Results are presented in equation form. New measurements are recommended as a consequence of this study. © 2006 Elsevier B.V. All rights reserved. PACS: 24.75.+i; 25.85.Ec; 25.85.Ca; 27.90.+b Keywords: Energy release and energy deposition in neutron-induced fission; Experiment and Los Alamos model; 235U; 238U; 239Pu 1. Introduction This study is a consequence of open questions on the magnitudes of the total prompt energy re- lease in fission, the total prompt energy deposition in fission, the components of these quantities, and their dependencies upon the kinetic energy of the neutron inducing the fission. Our results are given in Eqs. (31)–(33) and Fig. 17 for the total prompt energy release in fission, and in Eqs. -
Illllllllll DK9700033
Nordisk Nordisk Pohjoismamen Nordic kerne- karn- ydin- nuclear sikkerheds- sakerhcts- turvallisuus- safety forskning forskning uitkimus research RAK-2 NKS/RAK-2(96)TR-C3 Illllllllll DK9700033 Accidents in Nuclear Ships P. L. 01gaard Rise National Laboratory DK-4000 Roskilde, Denmark Institute of Physics Technical University of Denmark DK-2800 Lyngby, Denmark December 1996 Abstract This report starts with a discussion of the types of nuclear vessels accidents, in particular accidents which involve the nuclear propulsion systems. Next available information on 61 reported nuclear ship events is considered. Of these 6 deals with U.S. ships, 54 with USSR ships and 1 with a French ship. The ships are in almost all cases nuclear submarines. Only events that involve the sinking of vessels, the nuclear propulsion plants, radiation exposures, fires/explosions, sea-water leaks into the submarines and sinking of vessels are considered. For each event a summary of available information is presented, and comments are added. In some cases the available information is not credible, and these events are neglected. This reduces the number of events to 5 U.S. events, 35 USSR/Russian events and 1 French event. A comparison is made between the reported Soviet accidents and information available on dumped and damaged Soviet naval reactors. It seems possible to obtain good correlation between the two types of events. An analysis is made of the accident and estimates are made of the accident probabilities which are found to be of the order of 10"3 per ship reactor year It is finally pointed out that the consequences of nuclear ship accidents are fairly local and does in no way not approach the magnitude of the Chernobyl accident. -
Regulatory Guide 3.35, Revision 1
Revision 1 U.S. NUCLEAR REGULATORY COMMISSION July 1979 :*REGULATORY GUIDE OFFICE OF STANDARDS DEVELOPMENT REGULATORY GUIDE 335 ASSUMPTIONS USED FOR EVALUATING THE POTENTIAL RADIOLOGICAL CONSEQUENCES OF ACCIDENTAL NUCLEAR CRITICALITY IN A PLUTONIUM PROCESSING AND FUEL FABRICATION PLANT A. INTRODUCTION will review the proposal and approve its use, if found acceptable. Section 70.22, "Contents of Applications," of 10 CFR Part 70, "Domestic Licensing of Special B. DISCUSSION Nuclear Materials," requires, that each appli- cation for a license to possess and use special In the process of reviewing applications for nuclear material in a plutonium processing and permits and licenses authorizing the construc- fuel fabrication plant contain a description and tion or operation of plutonium processing and safety assessment of the design bases of the fuel fabrication plants, the NRC staff has principal structures, systems, and components developed a number of appropriately conser- of the plant. Section 70.23(a)(3) states that vative assumptions that are used by the staff applications will be approved if the Commission to evaluate an estimate of the radiological determines that, among other factors, the consequences of various postulated accidents. applicant's proposed equipment and facilities These assumptions are based on previous are adequate to protect health and minimize accident experience, engineering judgment, danger to life and property, and Sec- and on the analysis of applicable experimental tion 70.23(b) states that the Commission will results from safety research programs. This approve construction of the principal struc- guide lists assumptions used by the staff to tures, systems, and components of the plant evaluate the magnitude and radiological conse- when the Commission has determined that the quences of a criticality accident in a plutonium design bases of the principal structures, sys- processing and fuel fabrication plant. -
Fundamentals of Power Reactors Module One Science & Engineering Fundamentals
Training Centre / Centre de formation Fundamentals of Power Reactors Module One Science & Engineering Fundamentals Copyright Notice ©HER MAJESTY THE QUEEN IN RIGHT OF CANADA (1993) as represented by the Atomic Energy Control Board All rights reserved. No part of this publication may be reproduced, stored in a retrieval system or transmitted in any form or by any means, electronic, electrostatic, magnetic tape, mechanical photocopying, recording or otherwise, without permission from the Atomic Energy Control Board of Canada. Training Centre / Centre de formation Training Centre / Centre de formation Basis of Nuclear Structure and Fission Training Objectives The participant will be able to describe or understand: 1 the atomic and nuclear structure, 2 the basic vocabulary of nuclear energy: typical length scales, mass and energy units, etc., 3 the atomic and nuclear phenomena, 4 the fission and energy release processes, 5 the types of radiation, 6 the concept of neutron spectrum, 7 the conecpt of cross section 8 the concept of irradiation Nuc Struc & Fission Training Centre / Centre de formation Nuc Struc & Fission Training Centre / Centre de formation Basis of Nuclear Structure and Fission Table of Contents 1 Introduction ...............................................................................................3 2 Basics of Nuclear Physics ........................................................................4 2.1 Structure of the atom and nucleus ................................................4 2.1.1 Nuclear structure ..........................................................................4 -
SCA-TR-2016-SEC010, Argonne National Laboratory-West SEC-00224 Reactor Prioritization for Evaluation of ORAUT-OTIB-0054 Applicab
Draft ADVISORY BOARD ON RADIATION AND WORKER HEALTH National Institute for Occupational Safety and Health ARGONNE NATIONAL LABORATORY-WEST SEC-00224 REACTOR PRIORITIZATION FOR EVALUATION OF ORAUT-OTIB-0054 APPLICABILITY Contract No. 211-2014-58081 SCA-TR-2016-SEC010, Revision 0 Prepared by Stephen L. Ostrow, PhD SC&A, Inc. 1608 Spring Hill Road, Suite 400 Vienna, Virginia 22182 Saliant, Inc. 5579 Catholic Church Road Jefferson, Maryland 21755 July 2016 DISCLAIMER This is a working document provided by the Centers for Disease Control and Prevention (CDC) technical support contractor, SC&A for use in discussions with the National Institute for Occupational Safety and Health (NIOSH) and the Advisory Board on Radiation and Worker Health (ABRWH), including its Working Groups or Subcommittees. Documents produced by SC&A, such as memorandum, white paper, draft or working documents are not final NIOSH or ABRWH products or positions, unless specifically marked as such. This document prepared by SC&A represents its preliminary evaluation on technical issues. NOTICE: This report has been reviewed to identify and redact any information that is protected by the Privacy Act 5 U.S.C. § 552a and has been cleared for distribution. Effective Date: Revision No. Document No./Description: Page No. July 13, 2016 0 (Draft) SCA-TR-2016-SEC010 2 of 26 SC&A, INC.: Technical Support for the Advisory Board on Radiation & Worker Health Review of NIOSH Dose Reconstruction Program Argonne National Laboratory-West SEC-00224 Reactor Prioritization DOCUMENT TITLE: for -
Radiation Detection from Fission
ORNL/TM-2004/234 RADIATION DETECTION FROM FISSION J. T. Mihalczo DOCUMENT AVAILABILITY Reports produced after January 1, 1996, are generally available free via the U.S. Department of Energy (DOE) Information Bridge. Web site http://www.osti.gov/bridge Reports produced before January 1, 1996, may be purchased by members of the public from the following source. National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Telephone 703-605-6000 (1-800-553-6847) TDD 703-487-4639 Fax 703-605-6900 E-mail [email protected] Web site http://www.ntis.gov/support/ordernowabout.htm Reports are available to DOE employees, DOE contractors, Energy Technology Data Exchange (ETDE) representatives, and International Nuclear Information System (INIS) representatives from the following source. Office of Scientific and Technical Information P.O. Box 62 Oak Ridge, TN 37831 Telephone 865-576-8401 Fax 865-576-5728 E-mail [email protected] Web site http://www.osti.gov/contact.html This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. -
Introductory Nuclear Physics Problem Set 05
UNIVERSITY OF CAPE TOWN EEE4106Z: Introductory Nuclear Physics Problem Set 05 Due 1400 Tuesday 2 June 2015 This problem set should prove valuable in preparation for the final examination. The questions allow you to possibly gain a fuller understanding of important concepts that were not familiar to you at the time of preparing your answers to the preceding problem set. At Koeberg hand in to Z Isaacs. At UCT place in Aschman mailslot in mailboxes opposite room 508, top floor RW James Building UCT. Late answers will incur a penalty. Students may work together on the problems, and discuss the results together, but a handed-in script must be each student's own work. Copied work gets zero. Discuss the problems before tackling them! 1) Explain how the fuel temperature coefficient of reactivity is largely determined by the resonances in the cross-section for the 238U(n; γ) capture of neutrons. Provide a clear explanation of the Doppler broadening of the resonance peaks. SOLUTION: At higher temperatures there is greater thermal motion of the fuel nuclei, in particular U-238 nuclei. This increases the spread in the velocities, and hence the energies, with with the neutrons approach the U-238 nuclei. This causes Doppler broadening of the neutron capture resonances in the 238U(n; γ) cross-section in the epi-thermal energy region, so there is a greater chance of the a neutron being captured in the fuel as the neutron energy gets stepped down, from fast to thermal, by the moderator. This reduces the resonance escape factor p, and hence k. -
Inl Sec-00219 Reactor Prioritization for Evaluation of Oraut-Otib-0054 Applicability
Draft ADVISORY BOARD ON RADIATION AND WORKER HEALTH National Institute for Occupational Safety and Health INL SEC-00219 REACTOR PRIORITIZATION FOR EVALUATION OF ORAUT-OTIB-0054 APPLICABILITY Contract No. 211-2014-58081 SCA-TR-2016-SEC002, Revision 0 Prepared by Stephen L. Ostrow, PhD SC&A, Inc. 1608 Spring Hill Road, Suite 400 Vienna, Virginia 22182 Saliant, Inc. 5579 Catholic Church Road Jefferson, Maryland 21755 March 2016 DISCLAIMER This is a working document provided by the Centers for Disease Control and Prevention (CDC) technical support contractor, SC&A for use in discussions with the National Institute for Occupational Safety and Health (NIOSH) and the Advisory Board on Radiation and Worker Health (ABRWH), including its Working Groups or Subcommittees. Documents produced by SC&A, such as memorandum, white paper, draft or working documents are not final NIOSH or ABRWH products or positions, unless specifically marked as such. This document prepared by SC&A represents its preliminary evaluation on technical issues. NOTICE: This report has been reviewed to identify and redact any information that is protected by the Privacy Act 5 U.S.C. § 552a and has been cleared for distribution. Effective Date: Revision No. Document No./Description: Page No. March 2, 2016 0 (Draft) SCA-TR-2016-SEC002 2 of 36 SC&A, INC.: Technical Support for the Advisory Board on Radiation & Worker Health Review of NIOSH Dose Reconstruction Program INL SEC-00219 Reactor Prioritization for Evaluation of ORAUT- DOCUMENT TITLE: OTIB-0054 Applicability DOCUMENT NUMBER/ SCA-TR-2016-SEC002 DESCRIPTION: REVISION NO.: 0 (Draft) SUPERSEDES: N/A EFFECTIVE DATE: March 2, 2016 TASK MANAGER: John Stiver, MS, CHP PROJECT MANAGER: John Stiver, MS, CHP DOCUMENT John Stiver REVIEWER(S): Record of Revisions Revision Number Effective Date Description of Revision 0 (Draft) 03/02/2016 Initial issue NOTICE: This report has been reviewed to identify and redact any information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.